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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-041, Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods1998-03-0909 March 1998 Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods L-97-059, Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 9802151997-11-14014 November 1997 Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 980215 ML20141K7741997-04-24024 April 1997 Part 21 Rept Re Auxiliary Feedwater Check Valve Failure. Concluded Thermal Gradient Conditions Created by Flowing Cold Water Through Hot Valve Created Rapid Cooldown of Seat Ring,Allowing Ring to Displace ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20112D0101996-05-30030 May 1996 Part 21 Rept Re Possible Matl Defect in Certain Stainless Steel Swagelok Tube Fittings.List of Three Addl Shipments to Nuclear Facility of Parts Included in Investigation Encl ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML20092H3811995-09-12012 September 1995 Part 21 Rept Re Addl Defective Lot of 3/8-16x11/2 Hex Capscrews ASTM-A-193 Grade B7 from Which Orders Had Been Processed & Sold to Customers by Licensee ML20092H3761995-09-11011 September 1995 Part 21 Rept Re Mechanical Failures Discovered When Conducting Suppl Testing on Lot 3/8-24 X 2 A-193 B7 Hex Capscrews Identified by Head Markings ML20092A0361995-08-29029 August 1995 Part 21 Rept Re Mechanical Failures Discovered When Conducting Suppl Testing on 3/8-24 x2 A-193 B7 Hex Capscrews Identified by Head Markings ML20086T1761995-07-19019 July 1995 Part 21 Rept Re Potential Problem W/Type 51's & 87T Relays. Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML20072S4611994-09-0505 September 1994 Part 21 Rept Re Ssps semi-automatic Tester at Plant ML20073S9541994-06-27027 June 1994 Part 21 Rept Re Incorrect Matl Supply Discovered on Unshipped Order.Pump Div Will Notify Enertech W/ Recommendation That Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20070A1441994-06-22022 June 1994 Part 21 Rept Re Conditions Which Affect Hydraulic Valve Operators Supplied by Bw/Ip to Enertech Co & Listed Utils. Vendor Will Notify Enertech W/Recommendations That All Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20059E9081993-12-29029 December 1993 Part 21 Rept Re Decreases in Valve Actuator Motor Starting Torques Resulting from Increasing 3-Phase Actuator Motor Temp.Concludes Valves Capable of Performing Intended safety- Related Function ML20058K6431993-12-10010 December 1993 Part 21 Rept Re Potential for Unacceptable Recirculation Spray Sys Operation for Supporting Long Term Core Cooling Capability.Caused by Disc of motor-operated Valve on Suction of Pump Not Engaged to Motor Operator ML20058H0791993-12-0303 December 1993 Part 21 Rept Re BVPS Unit 2 Suction Valves for Rs Pumps Supplied by Henry Pratt Co,W/Regard to Inadequate Discharge Pressure.Temporary Mod Made to Four Affected Suction Valves Which Will Properly Position & Retain Spline Adapter ML20046B1321993-07-23023 July 1993 Interim Part 21 Rept Re Decreases in MOV Motor Starting Torques Resulting from Increasing Motor Temp.Valves Mfg by Limitorque Corp.Mfg in Process of Revising Recommended Torque Degradation Calculation at Degraded Voltage ML20128H4561993-01-25025 January 1993 Followup Part 21 Rept Re Disintegration of Balston 21554-1 Automatic Drain Float & Air Piping Filter Assemblies Mfg Prior to Nov 1989.Caused by Contaminants in Air Start Sys. Customers Should Order Air Filters Mfg After Nov 1989 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20116D1241992-10-29029 October 1992 Supplemental Part 21 Rept Re Byron Jackson River Water Pump Couplings.Initially Reported on 921101.Caused by Lack of Matl Toughness.Replacement Couplings Were Screened to Insure Adequate Toughness & Purchase Spec Amended ML20101R3691992-07-0707 July 1992 Final Part 21 Rept Re Failure of Byron Jackson River Water Pump Couplings.Initially Reported on 911121.Couplings Failed in Svc Due to Lack of Toughness.Couplings Examined & Suspect Matl Removed from Svc ML20079L8031991-11-0101 November 1991 Part 21 Rept Re 910620 Failure of Coupling in River Water Pump 1A Supplied by Byron Jackson.Caused by Mechanical Failure of Shaft Coupling.Metallurgical Analysis of Suspect Coupling Will Be Performed & Couplings Replaced ML20082P6871991-09-0404 September 1991 Revised Part 21 Rept Re Failure of Crosby Spring Relief Valves During Testing.Valve Prematurely Lifted During Sixth & Seventh Refueling Outages Due to Use of Stainless Instead of Carbon Steel.Springs,W/New Matl,Installed at Facility ML20077L5661991-08-0505 August 1991 Part 21 Rept Re Crosby Spring Relief Valve Failures Experienced During Testing at Facility.Evaluation Conducted to Determine If Safety Hazard Could Exist.Spring Changed to ASTM-A638 Grade 660,correcting Problem at Facility ML20055E8221990-07-0505 July 1990 Part 21 Rept Re Abb 27/59 Relays Deteriorated Due to Thermal Stress.Initially Reported on 900222.Units W/Listed Identification Numbers to Be Inspected & Replaced If Signs of Overheating Present ML20043A8491990-05-11011 May 1990 Part 21 Rept Re Contactors Used on Diesel Generator Immersion Heater Mfg by Cutler-Hammer.All Contactors W/Date Code Before 890522 Suspect.Dimensions Changed to Correct Problem.Formal Rept Will Be Sent Next Wk ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20236C7981987-10-22022 October 1987 Part 21 Rept Re Defect Concerning Modulating Solenoid Valve Supplied by Target Rock Corp.Valve Has Been Reassembled Using Proper Spiral Pin ML20237H8281987-08-0707 August 1987 Final Potential Significant Deficiency Rept 87-18 Re Failure of Emergency Switchgear & Diesel Generator Room Supply Fans to Start by Actuation of Switches on Alternate Shutdown Panel.Initially Reported on 870803.Control Switch Replaced ML20235M3651987-07-0101 July 1987 Deficiency Rept 87-09 Re Linear Indication on Reactor Vessel Weld.Initially Reported on 870301. Boat Sample Removed by Westinghouse for Vertical Linear Indication.No Addl Repts Anticipated ML20235H1811987-06-17017 June 1987 Final Deficiency Rept 87-16 Re Improper Installation of Bisco LOCA Seals in Conduits Containing Rockbestos Cable. Initially Reported on 870518.Rework on All Seals Completed ML20215C5771987-06-10010 June 1987 Part 21 Rept Re Small Leak in Unit B Cooling Water Header Lower Pipe in Right Bank of Emergency Diesel Generators. Affected Water Header Pipes Replaced W/Upgraded Matl & Unit a Water Header Pipes Visually Inspected for Leakage ML20215A9951987-06-0202 June 1987 Potential Significant Deficiency Rept 87-15 Re Failure of Main Steam Valve Area Supply Fans to Start Automatically. Initially Reported on 870508.Diesel Sequencer Interlock Rewired to Open Dampers.No Addl Repts Anticipated ML20215B0511987-06-0202 June 1987 Significant Deficiency Rept 87-14 Re Lack of Documentation Certifying Modes 5 & 6 N-1 Operation.Initially Reported on 870507.Appropriate Documentation Expected to Be in Place When Full Power License Received.No Addl Repts Required ML20215A3451987-05-29029 May 1987 Final Deficiency Rept 87-10 Re Linear Indications Identified During Preservice Insp of Reactor Vessel Studs.Initially Reported on 870501.Corrective Actions Include Blending/ Grinding of Surface Indications to Remove Distress Marks ML20214U9511987-05-28028 May 1987 Revised Final Deficiency Rept 87-08 Re Containment Isolation Phase B-initiated Timers for Control Room Emergency Pressurization Fans.Initially Reported on 870327.Correct Date for Completion Is 870504 Instead of 870411 ML20216C9341987-05-28028 May 1987 Potential Significant Deficiency Rept 86-14 Re Outside Containment Flood Analysis.Initially Reported on 860917. Outside Flood Analysis Calculation Revised to Elevate Lines Previously Exempted from Analysis ML20214J4911987-05-25025 May 1987 Interim Significant Deficiency Repts 87-16 & 87-17 Re Conduit Sealing of 50 Class 1E Items.All Physical Work Re Re Environ Qualification Program Complete W/Exception of Four Bisco Seals ML20214V0571987-05-21021 May 1987 Final Significant Deficiency Rept 87-07 Re High Head Safety Injection/ Charging Pump Operating Below Min Operating Curve.Initially Reported on 870323.Pump Rotating Assembly Replaced W/Spare Rotating Assembly & Satisfactorily Tested ML20214H4091987-05-14014 May 1987 Final Deficiency Rept 87-13 Re Pressure Locking & Thermal Binding of Westinghouse Gate Valves.Initially Reported on 870415.S&W Review Resulted in Initiation of Advance Change Notice D-0266 to Correct Discs in 10 Valves 1998-09-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30
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$YL 7TAb MAR 9 1982 (412)456 6000 436 $oth Avenue Pattatugh. Pa.
15219 United States Nuclear Regulatory Commission 2DLC Region I 4514 631 Park Avenue _
King of Prussia, PA 19406 @ %g T/
ATTENTION: Mr. R. Ilaynes 6s .,
'v Administrator l'E C ,w g +
m nw ,**I , .SS2 s SUDJECT: BEAVER VALLEY POWER STATION - UNIT 'NO. 2 -
DOCKET NO. 50-412 ~.. gc',j g kWyr.:
DEFECTIVE BROWN BOVERI OVERCURRENT RELAYS L) TTdi"# 1 /'
SIGNIFICANT DEFICIENCY 82-01, INTERIM REPORT NUMBE l
' g [?
Gentlemen:
This letter is Interim Report Number 1 concerning Significant Deficiency 82-01.
On January 28, 1982, Mr. J. Thomas of your office was notified by telephone of a potential significant deficiency in overcurrent relays manu-factured by Brown Boveri Electric, Inc. and provided for Beaver Valley Unit No. <
- 2. This was determined to be reportable in that, had it remained uncorrected,1 it could have adversely affected safe operation of the plant and it represents a significant deviation f rom performance specifications. The attached report provides a more detailed description of the problem. Duquesne Light Company will notify Region I when the corrective action is complete. This is expected to occur by August 27, 1982.
DUQUESNE LIGHT COMPANY BY E. J. WOOLEVER VICE PRESIDENT ATTACHMENT cc: NRC Document Control Desk Ms. E. Doolittle, Project Manager Mr. G. Walton, Resident Inspector 8203230258 820309 PDR ADOCK 05000412 S PDR f ,gS y s ty
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INTERIM REPORT NUMBER 1 ON SIGNIFICANT DEFICIENCY 82-01, DEFECTIVE BROWN BOVERI OVERCURRENT RELAYS AT BEAVER VALLEY POWER STATION - UNIT NO. 2 1.0
SUMMARY
< folid state overcurrent relays (Type ITE-50H and ITE-50D) manufactured by Brown Boveri Electric, Inc. (BBE) may malfunction by failing to drop out
'upon a reduction in current. These relays are designed to pick up when a
", g preset value is exceeded and to drop out when the current falls to a value of approxinately 98 percent of the preset value. Failure to drop out might inhibit the operation of a safety-related circuit.
2.0 DESCRIPTION
OF DEFICIENCY Sol'id state overcurrent relays (Type ITE-50H and ITE-50D) produced by BBE f rom 1976 through October 1980 may malfunction. These relays are designed as "high-dropout" units. This means that they should be self-resetting when the current drops slightly below the pickup setting. BBE published data states that the contacts should drop out when the input current to the relay falls below 98 percent of the pickup setting.
The nature of the potential problem is that the relay may not drop out upon the reduction in current. This is due to an integrated circuit designated as U4 on the drawout printed circuit board of the relay. The integrated circuit =is manufactured in two versions designated as the "A" chip and the 0,
"B" chip. These may be identified by the numbers 4047A or 4047B printed
( on the chip body. Only the relays manufactured with the "A" chip are susceptible to the problem described abote. However, testing has shown that not all of the "A" chips experience this failure.
The potentially defective relays are component parts of the 4KV switch-gear and diesel generator relay panels. As of this date, only the 4KV 3
switchgear has been delivered to the plant.
3.0 ANALYSIS OF SAFETY IMPLICATIONS A. BVPS-2 uses the ITE-50D relays in safety-related circuits. These relays are component parts of the 4KV switchgear units.
A.1 4kV - 480V Feeder Each redundant 4KV feeder to the redundant 480V emergency unit substations includes an ITE-50D to trip the 4KV breaker on over-current. All of the 1TE-50D relays supplied to BVPS-2 contain the potentially defective "A" chips.
CASE 1 The 50D includes an internal timer to permit coordination of its trip function with the downstream breaker protection. During normal operation, the 50D would be energized for a fault on the secondary of I
1 PAGE 2 the 480V unit substation. However, if the fault were cleared by a secondary device, .the 50D would drop out prior to operation of its internal timer and the subsequent energizing of its trip output relay. This sequence would allow the isolation of the faulted circuit while maintaining power to the remaining 480V substation 4
loads.
, The chip furnished with the BV-2 ITE-50D relays may disable this function and would thus cause the loss of the entire 480V load center under the above circumstances. Since the relays are used on i redundant 4KV feeders, loss of redundant emergency unit substations is possible and safe plant operation is jeopardized.
CASE 2 In the event of a safety injection signal (SIS), selected loads on both safety systems (4160V and 480V) receive simultaneous start signals. The pickup current setting on the 4KV feeder breaker relay 2
discussed above includes the inrush range of the combined starting load for the associated emergency system. As a result, it is possible that a simultaneous malfunction of both relays could occur which would initiate a trip to both emergency 480V substation breakers after their internal timers have timed-out and would jeopardize plant safety.
A.2 4KV-4KV Feeder 1 Each incoming supply f rom the normal 4KV buses to the redundant 4KV
- emergency buses also includes ITE-50D relays. These relays will j sense faults on the normal bus when the emergency diesel generator is i in the exercise mode. (In an accident condition, the diesel is j separated from the normal bus).
In the event that the 50D relays misoperate, as described above, and initiate separation of the emergency 4KV bus from its normal source of power, its safety function will not be impaired. Upon loss of normal power to the emergency bus, all required emergency loads would be step-loaded on the diesel.
B. BVPS-2 also uses the ITE-50D relays in the diesel generator protection relay circuits. Should these malfunction in a similar manner to the faults discussed above (A.1), the diesel generator output breaker would trip. This trip could jeopardize plant safety with the loss of diesel provided power.
4.0 IMMEDIATE ACTION TAKEN
. When BBE notified the Architect / Engineer identifying the potential problem with the overcurrent relays, two actions were immediately initiated:
PAGE 3 A. the overcurrent relays which BVPS-2 had received f rom BBE were disassembled to determine if they did in fact contain the integrated circuits which had been identified as being potentially defective, and B. an evaluation of the potential impact on the safe operation of the plant in the event of a ,9alfunction of the subject relays was begun.
When the evaluation indicated that the relays could have impact on plant safety, the Nuclear Regulatory Commission was notified.
5.0 CORRECTIVE ACTION TO REMEDY DEFICIENCY A. The defective relays have been removed from the emergency 4KV switchgear and returned to BBE for repair.
B. System Controls Corporation, the fabricator of the diesel generator protective relay circuits, has been notified of the problem with the relays. These relays have also been returned to BBE for repair.
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